ML20238E647
| ML20238E647 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/21/1987 |
| From: | Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GL-86-10, NUDOCS 8801050272 | |
| Download: ML20238E647 (4) | |
Text
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th Ch na Ebetric & Gas Cornya4 n
Columbia. SC 29??8 Nucear Operations (803) 748 3 13 SCE&G December 21, 1987 Document Control Desk U. S. Nuclear Regulatory Comission Wshington, DC 20555 ATTNi: John J. Hayas, Jr.
Subject:
Virgil C. hemmer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 l
Fire Protection Technical
{
Specification Amendment Request
Dear Mr. 'dayes:
As detailed in Mr. Hopkins's letter dated November 9, 1987, the attached pages have been amended to reflect deletion of the original wording in section 2.c.(18) of the Operating License and addition of the wording as recommended in Generic Letter 86-10. It is requested that these specific pages be substituted for those contaiu d in our originel submittal of March 31, 1987. This change has no effect on the Safety Evaluation or the Significant Hazards Determination. This change has been reviewed by the Plant Safety Review Committee and the Nuclear Safety Review Committee. This change will be implemented upon NRC approval end after the necessary procedural revisions have been incorporated.
If you have any questions, please advise.
l Ver tr 1 yo 3
xD.,d.i\\ u an %.
HIC / DAN:jez AttacFaert c:
D. W. Dixon, Jr./T. C. Nichols, Jr.
R. M. Campbell, Jr.
E. C. Roberts K. E. Nodland
- 0. S. Bradham J. C. Snelson D. R. Moore G. G. Ftreival W. A. Williams, Jr.
R. L. Prevatte J. N. Grace J. B. Knotts, Jr.
l Group Managers H. G. Shealy l
W. R. Baehr RTS R. B. Clary NPCF Aoc) h C. A. Price File C. L. Ligon (NSRC) 1
\\
8801050272 871221 ADOCK0500g5 DR
Attachment to Document Control Desk Letter December 21,.1987 Page 1:of 3 -
l (16) Cable Tray Separation (Section 8.3.3, SSER 4)
Prior to startup after the first refueling out-age, SCE&G shall implement the modifications to the cable trays discussed in Section 8.3.3 of Supplement No. 4 to the Safety Evaluation Report or demonstrate to the NRC staff that faults induced in non-Class lE cabla trays will not result in failure of cable in the adjacent Class lE cable trays.
(17) Alternate Shutdown System (Section 9.5.1, SSER 4 Prior to startup after the first refueling out-age, SCE&G shall install a source range neutron flux monitor independent of the control complex as part of the alternate shutdown system.
(18) Fire Protection System (Section 9.5.1, SSER 4)-
SCE&G shall maintain in effect, and fully J G.< e r / < 4,,/ 7 implement,.Al provisions of the approv..
ire protection plan, as amended thro (h A
nament No. 33 to the Final Safet na?.y-sis eport.
In addition, SCE&G shp 1 mainta'n the fire protection progfam set forth i ppendi.x R to 10 CFR P tt 50, except fo the following:
(1)
Twenty goot separat' n need not be betweep/' component cooling saihtaine' water pump B an C.
(ii)
Twenty-foot s p ration need not be maintained twe heating, ventila-tion, and ir. cond tioning system chilled ater pumps.
(iii)
Autoptic fire suppressi systems are N
regpired in the areas list in
/
(IM Supplement No. 3 to the Safe valuation Report with the exception
}'
g of the auxiliary building gas L
treatment filters.
( '
(i No automatic fire detector 0 are
.q L
required in the areas listed in Supplement No. 4 to the Safety Evaluation Report.
i
December ~21,1987 -
Page 2 of 3 J b.
Prior to startup after the first refue ng utage, SCE&G shall install and make er-a e a fire detection sytem in the reas lis d in Table 9-1 of Supplement /$o. 4 to the fety Evaluation Report.
ending instal tion of the fire dete ors in these areas th following actionb shall be taken:
(i)
Prior initi ly exceeding 5 per-cent of 11 ower, SCE&G shall, in lieu of Se ion 3.3.3.7 of the l
Technica S gcifications, establish a fire atch pqtrol to inspect each f
areaf very 2 hob s in accordance with Section 9.5.
of Supplement No.
4 to the Safety Eva uation Report.
(11 For all operating con 'tions subse-quent to initially excee ing 5 percent of full power, SC G shall comply with Section 3.3.3.7 f the
,/'
Technical Specifications.
(19) Instrument and Control Vibration Tests for Emergency Diesel Engine Auxiliary Support i
Systems (Section 9.5.4, SER)
Prior to startup after the first refueling outage, SCE&G shall either provide test results and results of analyses to the NRC staff for review and approval which validate the.t the skid-mounted control panels and mounted equip-ment have been developed, tested and qualified q
for operation under severe vibrational stresses encountered during diesel engine operation, or l
SCE&G shall floor mount the control panels l
presently furnished with the diesel generators I
separate from the skid on a vibration-free floor area.
(20) Solid Radioactive Waste Treatment System 1Section 11.2.3-,
SSER 4) l SCE&G shall not ship " wet" solid wastes from J
l the facility until the NRC staff has reviewed l
and approved the process control progran for l
the cement solidification system.
l l
a-__-___
e i e
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Attachment to Document Control Desk Letter December 21, 1987 Page 3 of 3 INSERT A Virgil C. Summer Nuclear Station shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility, and as approved in the SER dated February 1981 (and Supplements dated January 1982 and August 1982) and Safety Evaluations dated May 22, 1986, November 26, 1986 and July 27, 1987 subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
i l
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